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Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR

Journal Article · · Plasma Physics and Controlled Fusion
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  1. General Atomics, San Diego, CA (United States)
  2. Chinese Academy of Sciences (CAS), Hefei (China). Inst. of Plasma Physics
  3. Oak Ridge Associated Univ., Oak Ridge, TN (United States)
  4. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  5. Columbia Univ., New York, NY (United States)
  6. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  7. Huazhong Univ. of Science and Technology, Wuhan (China)
  8. Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA), Saint-Paul-Les-Durance (France)
  9. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center
  10. Univ. of California, Los Angeles, CA (United States). Dept. of Physics and Astronomy
Experimental and modeling investigations on the DIII-D and EAST tokamaks show the attractive transport and stability properties of fully noninductive, high poloidal-beta (βP) plasmas, and their suitability for steady-state operating scenarios in ITER and CFETR. A key feature of the high-βP regime is the large-radius (r>0.6) internal transport barrier (ITB), often observed in all channels (ne, Te, Ti, rotation), and responsible for both excellent energy confinement quality and excellent stability properties. Experiments on DIII-D have shown that, with a largeradius ITB, very high βN and βP values (both≥4) can be reached by taking advantage of the stabilizing effect of a nearby conducting wall. Synergistically, higher plasma pressure provides turbulence suppression by Shafranov shift, leading to ITB sustainment independent of the plasma rotation. Experiments on EAST have been used to assess the long pulse potential of the high-βP regime. Using RF-only heating and current drive, EAST achieved minute-long fully noninductive steady state H-mode operation with strike points on an ITER-like tungsten divertor. Improved confinement (relative to standard H-mode) and steady state ITB features are observed with a monotonic q-profile with qmin~1.5. Separately, experiments have shown that increasing the density in plasmas driven by lower hybrid wave broadens the q-profile, a technique that could enable a large radius ITB. These experimental results have been used to validate MHD, current drive, and turbulent transport models, and to project the high-βP regime to a burning plasma. These projections suggest the Shafranov shift alone will not suffice to provide improved confinement (over standard H-mode) without rotation and rotation shear. However, increasing the negative magnetic shear (higher q on axis) provides a similar turbulence suppression mechanism to Shafranov shift, and can help devices such as ITER and CFETR achieve their steady-state fusion goals.
Research Organization:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC52-07NA27344
OSTI ID:
1502029
Alternate ID(s):
OSTI ID: 23001440
Report Number(s):
LLNL-JRNL--758197; 943646
Journal Information:
Plasma Physics and Controlled Fusion, Journal Name: Plasma Physics and Controlled Fusion Journal Issue: 1 Vol. 60; ISSN 0741-3335
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

References (34)

GATO: An MHD stability code for axisymmetric plasmas with internal separatrices journal December 1981
An Eulerian gyrokinetic-Maxwell solver journal April 2003
A Fusion Nuclear Science Facility for a fast-track path to DEMO journal October 2014
Gyro-Landau fluid equations for trapped and passing particles journal October 2005
Tokamak profile prediction using direct gyrokinetic and neoclassical simulation journal June 2009
Physics basis of Multi-Mode anomalous transport module journal March 2013
Fast-ion transport in qmin>2, high- β steady-state scenarios on DIII-Da) journal May 2015
Progress toward steady-state tokamak operation exploiting the high bootstrap current fraction regime journal June 2016
The role of zonal flows in the saturation of multi-scale gyrokinetic turbulence journal June 2016
Confinement improvement in the high poloidal beta regime on DIII-D and application to steady-state H-mode on EAST journal May 2017
Gyrofluid simulations of turbulence suppression in reversed-shear experiments on the Tokamak Fusion Test Reactor journal May 1997
Reconstruction of current profile parameters and plasma shapes in tokamaks journal November 1985
Synergism between cross-section and profile shaping in beta optimization of tokamak equilibria with negative central shear journal October 1998
Alfvén eigenmode and energetic particle research in JT-60U journal September 1998
Sustainment of high confinement in JT-60U reversed shear plasmas journal February 2002
A review of internal transport barrier physics for steady-state operation of tokamaks journal March 2004
Stationary, high bootstrap fraction plasmas in DIII-D without inductive current control journal May 2005
Stationary high confinement plasmas with large bootstrap current fraction in JT-60U journal June 2005
Stability and dynamics of the edge pedestal in the low collisionality regime: physics mechanisms for steady-state ELM-free operation journal August 2007
Pedestal stability comparison and ITER pedestal prediction journal July 2009
ALOHA: an Advanced LOwer Hybrid Antenna coupling code journal November 2010
Advances towards QH-mode viability for ELM-stable operation in ITER journal July 2011
Quantitative comparison of experimental impurity transport with nonlinear gyrokinetic simulation in an Alcator C-Mod L-mode plasma journal April 2012
Compatibility of internal transport barrier with steady-state operation in the high bootstrap fraction regime on DIII-D journal November 2015
Multi-scale gyrokinetic simulation of tokamak plasmas: enhanced heat loss due to cross-scale coupling of plasma turbulence journal December 2015
Density limits in toroidal plasmas journal July 2002
Internal transport barriers: critical physics issues? journal April 2006
Full linearized Fokker–Planck collisions in neoclassical transport simulations journal December 2011
A versatile ray-tracing code for studying rf wave propagation in toroidal magnetized plasmas journal March 2012
Development of high poloidal beta, steady-state scenario with ITER-like tungsten divertor on EAST journal June 2017
Transport modeling of the DIII-D high ${{\beta}_{p}}$ scenario and extrapolations to ITER steady-state operation journal August 2017
Internal magnetic field measurements by laser-based POlarimeter-INTerferometer (POINT) system on EAST journal January 2016
Realization of minute-long steady-state H-mode discharges on EAST journal February 2017
Numerical Simulations of the Radio-Frequency–driven Toroidal Current in Tokamaks journal January 2014

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